ML22203A142
| ML22203A142 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 07/22/2022 |
| From: | Donnelly P Westinghouse |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| 55911, LTR-RAC-22-40 | |
| Download: ML22203A142 (1) | |
Text
WESTINGHOUSE NON-PROPRIETARY CLASS 3
© 2022 Westinghouse Electric Company LLC All Rights Reserved Director, Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852-2738 Direct tel: 803-647-1957 e-mail: donnelpb@westinghouse.com Your ref:
Our ref: LTR-RAC-22-40 July 22, 2022
SUBJECT:
60-Day Report Regarding the May 23, 2022 Incident Reported under 10 CFR 70 Appendix A 24-Hr Report, Columbia Fuel Fabrication Facility (License No. SNM-1107, Docket No. 70-1151)
REFERENCE:
NRC Event 55911 On May 24, 2022, the Columbia Fuel Fabrication Facility (CFFF) reported to NRC that two Items Relied on for Safety (IROFS) associated with the Waterglass Wastewater Treatment system had failed. This follow up report is being submitted to comply with 10 CFR 70.74(b).
Attached is a copy of the NRC Form 361A provided to the NRC Operations Center at the time of notification submitted to comply with 70.50(c)(2)(i) and the 60-day follow-up report, submitted to comply with 10 CFR 70.50 (c)(2)(ii-iv).
Please contact me at (803) 647-1957 should you have questions or need any additional information.
Patrick Donnelly Regulatory Affairs Manager Westinghouse Columbia Fuel Fabrication Facility Docket 70-1151 License SNM-1107 : NRC Form 361A associated with EN 55911 : Westinghouse 60-day Report for EN 55911 cc:
Mr. Thomas Vukovinsky Ms. Jennifer Tobin Westinghouse Electric Company LLC Columbia Fuel Site 5801 Bluff Road Hopkins, South Carolina 29061-9121 USA Patrick Donnelly (Jul 22, 2022 14:40 EDT)
Patrick Donnelly
WESTINGHOUSE NON-PROPRIETARY CLASS 3 Page 2 of 6 Our ref: LTR-RAC-22-40 July 22, 2022 NRC Form 361A associated with EN 55911
Page of NRC FORM 361A (09-2020)
U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER FUEL CYCLE AND MATERIALS EVENT NOTIFICATION WORKSHEET APPROVED BY OMB: NO. 3150-0238 EXPIRES: 10/31/2022 Estimated burden per response to comply with this voluntary collection request: 30 minutes. The information provided will be used for evaluation of licensee event description, facility status and for input to the public website. Send comments regarding burden estimate to the FOIA, Library, and Information Collections Branch (T-6 A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and the OMB reviewer at: OMB Office of Information and Regulatory Affairs, (3150-0238), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, Washington, DC 20503; e-mail: oira_submission@omb.eop.gov. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.
NRC FORM 361A (09-2020)
Continued on next page EN #
NRC OPERATIONS TELEPHONE NUMBERS: PRIMARY - 301-816-5100 or 800-532-3469, BACKUPS - [1st ] 301-951-0550 or 800-449-3694,
[2nd] 301-415-0550 and [3rd] 301-415-0553. Licensees who maintain their own ETS are provided these telephone numbers. FAX - 301-816-5151, EMAIL - hoo.hoc@nrc.gov Notification Time Facility or Organization License #
Name of Caller/Title Call Back #
Event Time & Zone Event Date Location of Event (Include County and State)
Portion of Plant Affected (If applicable)
EVENT CLASSIFICATIONS GENERAL EMERGENCY*
SITE AREA EMERGENCY ALERT NOTIFICATION OF UNUSUAL EVENT*
INCIDENT REPORT TRANSPORATION EVENT INFORMATION ONLY EVENT TYPES FUEL CYCLE MEDICAL / ACADEMIC TRANSPORTATION WASTE MANAGEMENT INDUSTRIAL/ COMMERCIAL FOREIGN EVENT OTHER (Specify)
OTHER (Specify)
INCIDENT REPORTS (30.50, 40.60, 70.50) 20.2201 LOSS / THEFT 20.2202 ACTUAL / THREATENED OVEREXPOSURE 20.2202 ACTUAL / THREATENED RELEASE 21.21 DEFECT / NONCOMPLIANCE 26.791 FITNESS FOR DUTY 35.3045 MEDICAL EVENT 36.83 IRRADIATOR EVENT 39.77 RUPTURED WELL LOGGING SOURCE 39.77 IRRETRIEVABLE WELL LOGGING SOURCE 40.26 TAILINGS / WASTE DAM FAILURE (a) PROTECTIVE ACTION PREVENTED (b)(1) UNPLANNED CONTAMINATION (b)(2) SAFETY EQUIPMENT FAILURE (b)(3) MEDICAL TREATMENT WITH CONTAMINATION (b)(4) FIRE / EXPLOSION 70.52 ACTUAL / ATTEMPTED THEFT APPENDIX A, 1-Hour APPENDIX A, 24-Hour CONCURRENT REPORT 70.52 CRITICALITY / SNM LOST
- ONLY UNDER OLD 1981 ORDER NOTIFICATIONS NRC REGION YES NO WILL BE STATE(s)
LOCAL OTHER GOVERNMENT AGENCIES PRESS RELEASE Anything Unusual or not understood?
Yes (Explain below)
No Did all systems function as required?
Yes No (Explain below)
Additional Information on page 2?
Yes No Event Description (Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc.) (Continue on Page 2) 1 2
55911 0902 Westinghouse SNM-1107 Patrick Donnelly, Reg Aff (803) 766-8157 0925 ET 05/23/2022 Hopkins, SC - Richland Co.
Administrative IROFS WT-165 and WT-166 require independent operators to sample and verify the V-1170 uranium concentration is below an administrative limit prior to discharge to the V-1160 tank. These IROFS were correctly performed on May 18, 2022 for both the V-1170A and V-1170B tanks. In between the 18th and the 23rd, the warm caustic filter was water washed with the process solution sent to the V-1170 tanks.
At 0422 on May 23, 2022, the contents of V-1170A and V-1170B tanks were pumped to the T-1160B tank without the tank uranium concentration being updated following the warm caustic filter wash.
At 0925 on May 23, 2022, an evaluation into the reportability of the event was initiated when a Uranium Recovery and Recycling Services (URRS) team manager contacted Criticality Engineering to report the transfer without the test results required by procedure. After reviewing updated tank test results, performing calculations to determine risk, and discussing actions taken by the operators, IROFS WT-165 and WT-166 were considered failed and IROFS WT-171, WT-172, WT-175 and WT-176 were considered degraded.
Page of NRC FORM 361A (09-2020)
FUEL CYCLE AND MATERIALS EVENT NOTIFICATION WORKSHEET (Continued)
U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER NRC FORM 361A (09-2020)
EN #
RADIOLOGICAL / CHEMICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS Isotope Activity Physical Form Chemical Form Stack Liquid Effluent Other (Specify)
Monitor Reading Alarm Setpoint Event Description (Continued) (Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc.)
ONGOING RELEASE TERMINATED RELEASE OFFSITE RELEASE ONSITE AREAS EVACUATED OFFSITE PROTECTIVE ACTION RECOMMENDED PERSONNEL EXPOSURE / CONTAMINATION DATA Number of Personnel Exposed Maximum External Dose Maximum Internal Dose Critical Organ (if known)
Critical Organ (if known)
Maximum Internal Level Maximum External Level Number of Personnel Contaminated Number and Types of controls necessary under normal operating conditions Number and Types of controls which functioned properly under upset conditions Number and Types of controls necessary to restore a safe situation Safety Significance of Events Safety Equipment Status Status of Corrective Actions 2
2 55911 Per CSE-15C-S1-G3, the remaining safety margin was 1.000E-2, which was below the required 1.000E-4.
The result is reportable per 10 CFR Part 70 Appendix A (b)(2), "Loss or degradation of items relied on for safety that results in failure to meet the performance requirements of 10 CFR 70.61."
Following the event, the contents of V-1170A and T-1160B were tested and historical tank level indication data was reviewed with results well within the IROFS limits. There was no safety impact as a result of the failed IROFS.
One active engineered control and six administrative controls.
The active engineered control (WCD-129) functioned properly.
The test results show the plant was in a safe condition and no limits were exceeded.
There was no safety impact as a result of the event. Tests performed on the tank contents following the event showed the tank contents and levels met IROFS requirements at the time of the transfer.
No equipment was impacted by the event and the plant is in a safe condition.
Warm caustic and cylinder recertification, which have similar IROFS for controlling inputs into 1160B tank, are all on hold pending review of extent of condition and corrective actions.
WESTINGHOUSE NON-PROPRIETARY CLASS 3 Page 5 of 6 Our ref: LTR-RAC-22-40 July 22, 2022 Westinghouse 60-day Report for EN 55911
WESTINGHOUSE NON-PROPRIETARY CLASS 3 Page 6 of 6 Our ref: LTR-RAC-22-40 July 22, 2022 Westinghouse 60-day report associated with Event No. 55911 Probable Cause of Event A sample was taken, analyzed and recorded on form CF-83-213 and verified by an operator to be under the maximum uranium concentration allowed for transfer of the V-1170 bank of favorable geometry tanks per IROFS WT-165. In addition, a second operator had confirmed that the test results were below the required uranium concentration and recorded on CF-83-213 form per IROFS WT-166. However, a part failure in the transfer line from the V-1170 tank to the non-favorable geometry T-1160B tank had delayed the transfer of the V-1170 tank contents by several days. During that delay, a filter had been water-washed adding to the contents of the V-1170 tanks and invalidating the samples. However, the procedure and associated form did not account for this scenario and the form was not annotated with a note to re-sample. When the transfer line was repaired, it appeared from the CF-83-213 form that all the IROFS had been completed and the operators initiated the transfer.
Corrective actions taken or planned to prevent occurrence of similar or identical events in the future and the results of any evaluations or assessments The associated procedure COP-835024 has been revised to specify that the V-1170 tanks shall be isolated and the valves locked when the tanks are sampled to preclude the addition of uranium into the tank and invalidate the sample results until the time of transfer.
Further, ISA-15, Wastewater Treatment System and associated calculation note CN-SB-09-06 have been updated to justify multiple failures of WT-165, WT-166, WT-171, WT-172, WT-175 and WT-176 before the incident would be considered reportable.
The controls on system inputs limit the uranium content such that more than 3 consecutive failures of the IROFS would have to occur before the uranium content in T-1160B would approach the conservatively calculated limits, even when considering maximum possible uranium concentrations.
Integrated Safety Analysis Evaluation This plant condition was considered in ISA Summary 15, Wasterwater Treatment System, Revision 16. Specifically, accident sequence CSE-15C-S1-G3.